ML19263E821

Amends 49 & 48 to Licenses DPR-32 & DPR-37,respectively, Revising Tech Spec Limits for Total Nuclear Peaking Factor

ML19263E821
Person / Time
Site:	Surry
Issue date:	05/09/1979
From:	Vollmer R Office of Nuclear Reactor Regulation
To:
Shared Package
ML19263E822	List: ML19263E821 ML19263E823 ML19263E824
References
NUDOCS 7906250332
Download: ML19263E821 (18)

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f UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTCN, D. C. 20555

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VIRGINIA ELECTRIC AND POWER COMPANY DOCXET N0. 50-280 SUROY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY CPERAT!NG LICENSE Amencment No. 49 License No. OPR-32 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The apolication for amendment by Virginia Electric and Power Company (the licensee) dated December 26, 1973, as sucplemented January 9,1979, complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I-,

B.

The facility will coerate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in ccmciiance with the Commission's regulations; D.

The issuance of this amencnent will not be inimical to the common defe._se and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations anc all applicable recuirements have been satisfied.

2214 134

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7 906250 33R

2-2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to the license amendment, and paracraph 3.3 of Facility Operating License No. OPR-32 is hereby amended to read as follows:

B.

Technical Soecification The Technical Specifications contained in Appendices A ano 3, as revised through Amendment No. 49, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

License Exemption dated June 30, 1978 is hereby terminated.

4.

This license amencment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATCRY COMMISSION

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1 A'W'Lw w

R. H. Vollmer, Assistant Director for Systems and Projects Division of Operating Reactors Attachnent:

Changes to the Technical Specifications Date of Issuance: May 9,1979 2214 135

p= 4:w*g UNITED STATES y

-.1 NUCLEAR REGULATORY CO*.tMISSION

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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPEfAT!NG LICENSE Amendment No. 48 License No. DPR-37 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Virginia Electric and Power Company (the licensee) dated Decem.ber 26, 1978, as supplemented January 9,1979, ccmolies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chacter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the oublic; and E.

The issuance of this amendment i t in accordance witn 10 CFR Dart 51 of the Commission's regulations and all acclicable recuirements have been satisfied.

2214 136

• m 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to the license amendment, and paragraph 3.5 of Facility Operating License No. OPR-37 is amended and 3.H. is added to read as follows:

B.

Technical Scecification The Technical Specifications contained in Ap;endices A and B, as revised through Amendment No. 48, are heresy incorporated in the license. The licensee shat ! Operate the facility in accordance with the Technical Specifications.

H.

The steam generator for Unit 2 shall not exceed a tube plugging level of 5" until approved by the NRC.

3.

The Order for Modification of License dated April 28, 1973 is herecy t ermi nat ed.

4.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATCRY COMMISSION Ubok-C/CV

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.. w R. H. Vollmer, Assistant Di ector for Systems and Projects Division of Operating Reactors

Attachment:

Changes to the Technical Specifications Date of Issuance: May 9, 1979 2214 137

ATTACF'1ENT TO LICENSE A!!ENDMENT NOS. 29 AND 43 FACILITY OPERATING LICEt:SE NCS. OPR-32 AND CPR-37 COCKET NOS. 50-280 AND 50-231 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Arenament number and contain vertical lines indicating the area of change.

Remove Insert 3.3-1 3.3-1 3.12-4 3.12 0 3.12 Ja 3.12 4a 3.12-5 3.12-5 3.12-6 3.12-6 3.12-7 3.12-7 3.12-14 3.12-la 3.12 -14 a 3.12-17 3.12-17 3.12-21 3.12-21 Table 3.12-la Table 3.12-l a Table 3.12-2 Table 3.12-2 Figure 3.12-8 Figure 3.12-8 Figure 3.12-10 2214 138

TS 3.3-1 3.3 SAFETY INJECTION SYSTEM Acolicability Applies to the operating status of the Safety Injection Syste=.

Objective To define those limiting conditions for operation that are necessary to provide sufficient borated cooling water to remove decay heat from the core in e:ergency situations.

Soecifications A.

A reactor shall not be made critical unless the following conditions are

=et:

1.

The refueling water tank contains not less than 350,000 gal. of borated T

water with a boron concentration of at least 2000 ppm.

2.

Each accu =ulator system is pressurized to at least 600 psia and con-tains a minimum of 975 ft3 and a maxi =u= of 989 ft3 of borated water with a boron concentration of at least 1950 ppe.

3.

The boron injection tank and isolated portion of the inlet and outlet piping contains no less than 900 gallons of water with a boron concentration equivalent to at least 11.5% to 13% weight boric acid solution at a temperature of at least 1450F. Additionally, recirculation between a unit's Boron Injection Tank and the Soric Acid Tank (s) assigned to the unit shall be maintained.

2214 139 Amendment No. 49, Unit i Amendment No. 28, Unit 2

TS 3.12-4 Fq(Z) < 2.05/P x K(Z) for P >.5 Fq(2) < 4.10 x K(Z) f or P

<.5 F{H < l.55 (1 + 0.2(1-P)) x T(BU)

FN LOCA

< l.38/P AH Asso. -

FN LOCA

<l.45/P AH Rod where P is the fraction of rated power at which the core is operating, K(Z) is the function given in TS Figure 3.12-8, Z is the core height l

location of Fq, and T(BU) is the interim thimble cell rod bow penalty onFfg given in TS Figure 3.12-9.

2.

Prior to exceeding 75% power following each core loading, and during each ef fective full power month of operation thereaf ter, power distribution

=aps using the covable detector system, shall be made to confirm that the hot channel factor limits of this specification are satisfied.

For the purpose of this confirmation:

Themeasurementoftotalpeakingfactor,F{eas.,shallbeincreased a.

by eight percent to account for manufacturing tolerances, measure-ment error, and the effects of rod bow.

The =easurement of enthalpy rise hot channel factor, the hot assembly enthalpy rise factor,

~

N LOCA N

LOCA ThH Assm..andthehotrodenthalpyrisefactor,FhH, Rod j shall be increased by four percent to account for measurement error.

If any I

measured hot channel factor exceeds its limit specified under 3.12.B.1, the reactor power and high neutron flux trip setpoint shall be reduced until the limits under 3.12.B.1 are met.

If the hot channel factors cannot be brought to within the limits Q _< 2.05 x K(Z), FfH F

d 2

H Ffg

_ l.38 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the Overpower AT and Overtempera-ture AT trip setpoints shall be similarly reduced.

2214 140 Amendment No. 49, Unit 1 3,1,:33 Amendment No. 48, 'Jnit 2

~~

TS 3.12-;a i,

b.

F (Z) shall be evaluated for nor=al (Condition I) operation of q

Unit 2 by conbining the measured values of Fxy(Z) with the design Condition I axial peaking factor values, F (Z), as listed.in TS Z

Table 3.12-1B.

For the purpose of this specification Fxy(Z) shall be determined between 1.5 feet and 10.5 feet elevations of the core exclusive of grid plane regions located at 25.9 3.2 inches, 52.1 13.2 inches, 78.3 13.2 inches, and 104.5 23.2 inches. The measured values of Fxy(Z) shall be increased by nine percent to account for nanufacturing tolerances, measure =ent error, rod bow, xenon redistribution, and any burnup dependent peaking factor increases.

If the results of this evaluation predict that F (Z)

Q could potentially violate its limiting values as established in Spec'fication 3.12.B.1, either:

(1) the thermal power and high neutron flux trip setpoint shall be reduced at least 1% for each 1% of the potential violation (for the purpose of this specification, this power level shall be called PTHRESHOLD), or-(2) movable detector surveillance shall be required for operation when the reactor ther=al power exceeds ?THR2.SHOLD. This sur-veillance shall be perfor=ed in accordance with the following:

d (a)

The nor=ali:ed power distribution, Fq(Z)

APDM' ##

• thimble j at core elevation 2 shall be measured utilizing f

at least two thimbles of the movable incore fi.:x system for i

t 2214 141 Amendment tio. 49, Unit 1 Amendment !!o. 48, Unit 2

TS 3.12-5 3.

The reference equilibrium indicated axial flux difference (called the target flux difference) at a given power level P, is that o

indicated axial flux difference with the core in equilibrium xenon canditions (small or no oscillation) and the control rods more than 190 steps withdrawn. The target flux difference at any other power level, P, is equal to the target value of P cultiplied by the ratio, P/P. The target flux difference shall be measured at least once o

per equivalent full power quarter. The target flux difference must be updated during each effective full power month of operation either by actual ceasure=ent, or by linear interpolation using the most recent value and the value predicted for the end of the cycle life.

l 4.

Except as modified by 3.12.B.4.a, b, c, or d below, the indicated axial flux difference shall be maintained within a tS7. band about the target flux difference (defines the target band on axial flux difference),

s. At a power level greater than 88 percent of' rated power, if l

the indicated axial flux difference deviates from its target band, within 15 minutes either restore the indicated axial flux difference to within the target band, or reduce the reactor power to less than 88 percent of rated power.

b. At a power level no greater than 88 percent of rated power, (1) The indicated axial flux difference may deviate from its target band for c max 1=um of one hour (cuculative) in any 2I.-hour period provided the flux dif f erence is within the limits shown on Figure 3.12-10.

2214 142 Amendment No. 49, Unit 1 Amendment No. 48, Unit 2

ra s.sa ;

One minute penalty is accu =ulated for each one minute of operation outside of the targat band at power levels equal to or above 50% of rated power.

(2)

Il 3.12.B.4.b(1) is violated, then the reactor power shall be reduced to less than 50% power within 30 minutes and the high neutron flux setpoint shall be reduced to no greater than 55% power within the next four hours.

(3)

A power increase to a level greater than 88 percent of rated power is contingent upon the indicated axial flux difference being within its target band.

(4)

Surveillance testing of the Power Range Neutron Flux Channels may be performed pursuant to Table 4.1-1 provided the indicated AFD is =aintained within the limits of Figure 3.12,10.

A total rf 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> of operation may be accu =ulated with the AFD outside of the target band during this testing without penalty deviation,

c. At a power level no greater than 50 percent of rated power, (1)

The indicated axial flux difference may deviate fro = ir.s target band.

(2) A power increase to a level greater than 50 percent of rated power is contingent upon the indicated axial flux difference not being outside its target band for = ore than one hour accu =ulated penalty during the preceding

~

24-hour period. One half minute penalty is accumulated for each one =inute of operation outside of the targat band at power levels between 15% and 50% of rated power.

l

d. The axial flux difference limits of Specifications 3.12.3.4.a, b, and c may be suspended during the perfor=ance of physics tests provided:

(1)

The power level is maintained at or below 85% of rated power, and (2)

The limits of Specification 3.12.B.1 are maintained.

The power level shall be determined to be _<_85% of rated pcwer at least once per hour during physics tests. Verification that the limits of Specification 3.12.B.1 are being met shall be demonstrated through in-core flux =apping at least once per 2214 143 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Amendment flo. 49, Unit 1 Amendment No. 48, Unit 2

~

TS 3.12 s Alar =s shall normally be used to indicate the deviations fron the axial flux difference requirements in 3.12.B.4.a and the flux difference ti=e limits in 3.12.B.4.b and c.

If the alar:s are out of service te=porarily, the axial flux difference shall be logged, and conformance to the li=its assessed, every hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and half-hourly thereafter.

The indicated axial flux difference for each excore channel shall be uonitored at least once per 7 days when the alarm is operabl nd at least once per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after restoring the alarm to operable status.

5.

The allowable quadrant to average power tilt is 2.0%.

6.

If, except for physics and rod exercise testing, the quadrant to average power tilt exceeds 2%, then:

a.

The hot channel factors shall be deter =ined within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and the power level adjusted to meet the specification of 3.12.B.1, or b.

If the hot channel factors are not deter =ined within two hours, the power level and high neutron flux-trip setpoint shall be reduced from rated power, 2% for each percent of quadrant tilt, c.

If the quadrant to average power tilt exceeds 10%, the power level and high neutron flux trip setpoint will be reduced from rated power, 2% for each percent of quadrant}f j44 tilt. Amendment No. 49, Unit 1 Amendment No. 48, Unit 2

TS 3.12-14. Eq(2), Height Decendent Heat Flux Het Channel Factor, is defined as the max 1=u= local heat flux on the surface of a fuel red at core elevation Z divided by the average fuel red heat flux, allowing for manufacturing tolerances on fuel pelle*a and rods. . h, Engineerine Heat Flux Hot Channel Factor, is defined as the allowance on heat flux required for canufacturing tolerances. The engineering factor allows for local variations in enrichment, pellet density and dia=eter, surface area of the fuel rod and eccentricity of the gap between pellet and clad. Co=bined statistically the net effect is a factor of 1.03 to be applied to fuel rod surface heat flux. F{H,NuclearEnthalpyRiseHotChannelFactor,isdefinedastheratioof the integral of linear power along the rod with the highest integrated power to the average rod power for both LOCA and non-LOCA considerations. F , Hot Asse=bly Nuclear Enthaley Rise Factor, is defined as the H ratio of the integral of linear power along the asse=bly with the highest integrated power to the average assembly power. It should be noted that the enthalpy rise factors are based on integrals and are used as such in the DNB and LOCA calculations. Local heat flu"xes a obtained by using hot channel and adjacent channel explicit power shapes which take into account variations in radial (x-y) power shapes throughout the core. Thus the radial power shape at the point of cax1=u= heat flux is not necessarily directly related to the enthalpy rise fattors. The results of the loss of coolant accident analyses are conservative with respect to the ECCS acceptance criteria as specified in 10 CFR 50.46 using an upper bound envelope of 2.05 ti=es the hot channel f actor nor=alized cperating envelope given by TS Figure 3.12-8. Amendment No. 49, Unit i Amendment No. 48, Unit 2 ~

TS 3.1^-17 For normal (Condition I) operation of Unit 2, it cay be necessary to perform surveillance to insure that the heat flux hot channel factor, Fq(Z), limit is cet. To deter =ine whether and at what power level surveillance is required, the potential (Condition I) values of Fq(Z) shall be evaluated conthly by com-bining the ceasured values of Fxy(Z) obtained from the analysis of the monthly incore flux cap with the values of the design Condition I axial peaking f actors, F (Z). The product of these shall be increased by nine percent to account for Z =easurement uncertainty, =anufacturing tolerances, rod bow, radial redistribution of xenon during nor=al (Condition I) operation, and any burnup dependent peak-ing factor increases. PTHRESHOLD is defined as the value of rated power minus one percent power for each percent of potential F (Z) violation. If the potential Q values of F (Z). for nor=al (Condition I) operation are greater than the Fq(Z) Q limit, then surveillance shall be performed at all power levels above PTHRESHOLD' Movable incore instrumentation thimbles for surveillance are selected so that the ceasurements are representative of the peak core power density. By li=iting the core average axial power distribution, the total power peaking factor F (Z) can be limited since all other components remain Q relatively fixed. The re=aining part of the total power peaking factor can be derived based on incore measurements, i.e., an effective radial peaking factor, R, can be determined as the ratio of the total peaking 2214.146 Amendment ?;o. 49, Unit i Amendment flo. 48, Unit 2

TS 3.12-21 ~ power and allowance has been nade in predicting the heat flux peaking factors for less strict control at part power. Strict control of the flux dif ference is not always possible during certain physics tests or during excore detector calibrations. Therefore, the specifications on power distribution control are less restrictive during physics tests and excore detector calibrations; this is acceptable due to the low probability of a signi-ficant accident occurring during these operations. In so=e instances of rapid unit power reduction automatic rod cotton vill cause the flux difference to deviate from the target band when the reduced power level is reached. This does not necessarily affect the xenon dis-l tribution sufficiently to change the envelope of peaking factors which can be reached on a subsequent return to full power within the target band; however to si=plify the specification, a licitation of one hour in any period of 24 hours is placed on operation outside the band. This ensures that the resulting xenon distributions are not significantly different fro = those resulting.from operation within the target band. The instan-l taneous consequences of being outside the band, provided rod insertion ~ limits are observed, is not worse than a 10 percent increment in peaking f actor for that allowable flux difference at 88*. power, in the range +13.5 g percent (110.5 percent indicated) where for every 2 percent below rated power, the permissible flux difference boundary is extended by 1 percent. As discussed above, the essence of the procedure is to maintain the xenon distribution in the core as close to the equilibrium full power condition 2214.147 Amendment No. 49, Unit 1 Amendment No. 48, Unit 2 ~

TS Table 3.12-1A THIS TABLE HAS BEEft DELETED 2214 l'48 Amendment ?!o. 49, Unit 1 ~ Amendment flo. 28, Unit 2

to u.i= .,.u.. I I i i e l THIS TABLE HAS BEEN DELETED s l Amendment ifo. 49, Unit 1 Amendment No. 48, Unit 2 2214 149

~ ~ TS FIGU*.I 3.12.S y J d kl I HOT CHANNEL FACTOR NOPl!ALIZED OPERATING E'NELOPE SUF3Y POWER STATION UNIT NOS.1 A'O 2 I i i t j l ! ! I I I 1 i l l l l i i l i l i l'

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} g .I i i l I I I i 1 I i i i I l\\ j [~ - [ '\\ j i j -J T-503 i, i, l l \\l c {' l I \\i N i 8 .i: l j- .\\ i. y ? ..\\ { i s 0.6 i il 2 g 5_. 5 9 l I I I l l l 1 I R l l 1 l ,.. l [ v x 0.4 g g i i i i F i l I I L _.._ ja _.. I I_ I4 ' I I I 0.2 l l l:- l i t i I I l i. 0 2 4 6 8 10 12 r CORE HEIGHT (FT.) 2214 150 Ar.endment No. 29, Unit 1 Amendment ~~. IS, Uni: 2

TS FI-.'?.I 3.12-10 P00R s.......w AXIAL FLUX DIFFEFINCE LIMITS AS A FUNCTICN OF RATED POWER <t'uoy now n e as -m** I e c. 1-120

r. :-

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. := .-..e n i .2; ~ ' = ~~2-i - ' - --F ~ - li~- .:.5.. E,. _. _ _ _..; i.._".E.C__ 5 .'_i 7d . i!i -. !_9_._..E_.... E,. E'J.. 20 . - - - g_. ..g: :- _.. __A.. .g; u I -i ~ 'j'~ l 0 1 -50 -40 -30 -20 -10 0 10 20 30 40 50 FLUX DIFFERENCE (AI) 7. 's' 2214 151 Amendment t!o. 49, Unit 1 Amendment No. 48, Unit 2

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